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Title: State-of-the-Art Reactor Conseuqence Analsyes (SOARCA) Project.


Abstract not provided.

Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
OSTI Identifier:
Report Number(s):
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: Proposed for presentation at the Nuclear Energy Expert Group Meeting held September 18-20, 2016 in Singapore, NA, Singapore.
Country of Publication:
United States

Citation Formats

Osborn, Douglas. State-of-the-Art Reactor Conseuqence Analsyes (SOARCA) Project.. United States: N. p., 2016. Web.
Osborn, Douglas. State-of-the-Art Reactor Conseuqence Analsyes (SOARCA) Project.. United States.
Osborn, Douglas. 2016. "State-of-the-Art Reactor Conseuqence Analsyes (SOARCA) Project.". United States. doi:.
title = {State-of-the-Art Reactor Conseuqence Analsyes (SOARCA) Project.},
author = {Osborn, Douglas},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2016,
month = 8

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  • The Kyoto Univ. Research Reactor Inst. (KURRI) has a plan to operate the Accelerator Driven Subcritical Reactor (ADSR) by using the Fixed Field Alternating Gradient (Fag) accelerator, which is a synchrotron-type accelerator developed in the High Energy Accelerator Research Organization (KEK) of Japan. In this ADSR, high-energy neutrons generated by interaction of 150 MeV proton beam with heavy metal will be injected into a solid-moderated and -reflected thermal core (A-core) of the Kyoto Univ. Critical Assembly (KUCA) in the KURRI. At the A-core, a series of preliminary experiments had been carried out for examination of neutronic characteristics in the ADSRmore » by using 14 MeV pulsed neutron generator combined with the A-core. The static and dynamic parameters were evaluated in the subcritical systems: neutron multiplication, neutron decay constant, reaction rate distribution, neutron spectrum and subcriticality. The numerical analyses for the experiments had been executed by using Monte Carlo calculation code MCNP-4C3 coupling with nuclear data libraries: ENDF/B-VI.2 and JENDL-3.3. From the comparison between the experiments and the calculations, it was obtained with the results very important and valuable for a new ADSR with the FFAG accelerator. After the injection by the FFAG accelerator, both new experiments and numerical simulations could be conducted for the high-energy neutrons generated by 150 MeV proton beam. (authors)« less
  • The REVE (Reactor for Virtual Experiments) project is an international joint effort aimed at developing multi-scale modelling computational toolboxes capable of simulating the behaviour of materials under irradiation at different time and length scales. Well grounded numerical techniques such as molecular dynamics (MD) and Monte Carlo (MC) algorithms, as well as rate equation (RE) and dislocation-defect interaction theory, form the basis on which the project is built. The goal is to put together a suite of integrated codes capable of deducing the changes in macroscopic properties starting from a detailed simulation of the microstructural changes produced by irradiation in materials.more » To achieve this objective, several European laboratories are closely collaborating, while exchanging data with American and Japanese laboratories currently pursuing similar approaches. The material chosen for the first phase of this project is reactor pressure vessel (RPV) steel, the target macroscopic magnitude to be predicted being the yield strength increase ({delta}{sigma}y) due, essentially, to irradiation-enhanced formation of intragranular solute atom precipitates or clouds, as well as irradiation induced defects in the matrix, such as point defect clusters and dislocation loops. A description of the methodological approach used in the project and its current state is given in the paper. The development of the simulation tools requires a continuous feedback from ad hoc experimental data. In the framework of the REVE project SCK EN has therefore performed a neutron irradiation campaign of model alloys of growing complexity (from pure Fe to binary and ternary systems and a real RPV steel) in the Belgian test reactor BR2 and is currently carrying on the subsequent materials characterisation using its hot cell facilities. The paper gives the details of this experimental programme - probably the first large-scale one devoted to the validation of numerical simulation tools - and presents and discusses the first available results, with a view to their use as feedback for the improvement of the computational modelling. (authors)« less
  • Abstract not provided.